CONVECTIVE DRY FILTERED CONTAINMENT VENTING SYSTEM
    1.
    发明申请
    CONVECTIVE DRY FILTERED CONTAINMENT VENTING SYSTEM 审中-公开
    对流干燥过滤装置系统

    公开(公告)号:WO2016011055A2

    公开(公告)日:2016-01-21

    申请号:PCT/US2015/040413

    申请日:2015-07-14

    Applicant: AREVA INC.

    CPC classification number: G21C13/022 G21C9/004 G21C19/303 G21F9/02 Y02E30/40

    Abstract: A dry FCVS for a nuclear reactor containment is provided. The dry FCVS includes a housing and a round and/or elongated aerosol filter inside the housing for removing contaminant aerosols from gas passing through the housing during venting of the containment. The housing includes at least one inlet portion configured for directing gas into the aerosol filter during the venting of the containment and an outlet portion for gas filtered by the aerosol filter during the venting of the containment. The dry filtered containment venting system is arranged and configured such that when a flow of gas through the outlet portion is closed off at least one of convective, radiant and conductive heat transfer removes decay heat of aerosols captured in the aerosol filter.

    Abstract translation: 提供了一个用于核反应堆遏制的干式FCVS。 干式FCVS包括壳体和壳体内的圆形和/或细长的气溶胶过滤器,用于在通风期间从通过壳体的气体中除去污染气溶胶。 壳体包括至少一个入口部分,其构造成用于在泄放容纳物期间将气体引导到气溶胶过滤器中,以及用于在排气期间由气溶胶过滤器过滤的气体的出口部分。 干燥过滤的容纳排气系统被布置和构造成使得当通过出口部分的气体流被封闭时,至少一个对流,辐射和导电的热传递去除了在气溶胶过滤器中捕获的气溶胶的衰变热。

    VENT ASSEMBLY
    3.
    发明申请
    VENT ASSEMBLY 审中-公开
    通风装置

    公开(公告)号:WO1993009542A1

    公开(公告)日:1993-05-13

    申请号:PCT/US1992005655

    申请日:1992-07-06

    CPC classification number: G21C13/022 G21D1/02 Y02E30/40

    Abstract: A vent tube (66) and housing nut (62) replace the original housing plug (52) on a pressurized water nuclear reactor. The vent tube engages the installed vent stem (38) cross-slot (48) with a cross-shaped projection (70). During operation, the vent tube (66) is pushed down to engage the vent stem (38) and rotated to allow vented air to travel through stem (38) and tube (66). After venting, the vent stem is rotated back and tightened. The invention provides visual indication of a leaking ball (32) since any leakage lifts vent tube (66). Time required for venting is reduced and no removal of installed ball seal (32, 34), a proven primary seal, is required.

    CONTAINMENT-SCHUTZSYSTEM FÜR EINE KERNTECHNISCHE ANLAGE UND ZUGEHÖRIGES BETRIEBSVERFAHREN
    4.
    发明申请
    CONTAINMENT-SCHUTZSYSTEM FÜR EINE KERNTECHNISCHE ANLAGE UND ZUGEHÖRIGES BETRIEBSVERFAHREN 审中-公开
    进行核设备收纳保护系统和相关工作程序

    公开(公告)号:WO2014019770A1

    公开(公告)日:2014-02-06

    申请号:PCT/EP2013/063153

    申请日:2013-06-24

    Applicant: AREVA GMBH

    Abstract: Ein Containment-Schutzsystem (2) zur Behandlung der im Containment (4) einer kerntechnischen Anlage (6), insbesondere eines Kernkraftwerks, befindlichen Atmosphäre bei kritischen Störfällen mit massiver Freisetzung von Wasserstoff (H 2 ) und Dampf soll dazu in der Lage sein, derartige Zustände auf überwiegend passive Weise und möglichst ohne Belastung der Umgebung effektiv und schnell abzubauen. Zu diesem Zweck weist das Containment-Schutzsystem (2) erfindungsgemäß einen ein Leitungssystem (10, 72, 120, 128) umfassenden, zum Anschluss an das Containment (4) vorgesehenen Kreislauf aus dem Containment (4) und wieder zurück für einen Fluidstrom auf, und zwar mit zumindest folgenden strömungsmäßig in Reihe geschalteten Komponenten: eine Rekombinationsvorrichtung (20) zur Rekombination von im Fluidstrom enthaltenem Wasserstoff (H 2 ) mit Sauerstoff (O 2 ) zu Wasserdampf (H 2 O); eine der Rekombinationsvorrichtung (20) nachgeschaltete Kondensationsvorrichtung (74) zur Kondensation von im Fluidstrom enthaltenen Dampfanteilen mit Mitteln zur Ableitung des Kondensats (94) aus dem Fluidstrom; Antriebsmittel (18, 180) für den Fluidstrom, wobei für eine zumindest teilweise Rückkühlung der Kondensationsvorrichtung (74) ein Wärmetauscher (96) vorhanden ist, der eingangsseitig über eine Zufuhrleitung (144) mit einem Vorratsbehälter (140) für flüssigen Stickstoff (N 2 ) verbunden ist.

    Abstract translation: 甲容纳保护系统(2),用于容纳的处理(4)核设施的(6),特别是核电厂,在用氢气(H2)的大量释放和蒸汽临界事故位于气氛为能够在这样的条件 在主要被动的方式,如果有可能,不污染环境的有效和迅速减少。 为了这个目的,密封保护系统(2)根据本发明的导线系统(10,72,120,128),其包括用于连接到用于流体流动到设置用于循环从容纳(4),然后再返回所述容纳(4), 以及与至少以下流体地串联连接的部件:重组设备(20),用于重组包含氢的流体流(H2)和氧气(O2),以形成水蒸汽(H 2 O)中; 复合装置的一个(20)下游的冷凝装置(74),用于冷凝包含在流体流部分有用于从流体流中的冷凝物(94)的排出蒸汽; 驱动装置(18,180),用于将流体流,其中,用于所述冷凝装置(74)的热交换器(96)的至少部分地再次冷却经由连接到用于液体氮的贮存器(140),一个电源线(144)设置在输入侧(N2) 是。

    METHOD AND DEVICE FOR VENTING THE PRIMARY CIRCUIT OF A NUCLEAR REACTOR
    7.
    发明申请
    METHOD AND DEVICE FOR VENTING THE PRIMARY CIRCUIT OF A NUCLEAR REACTOR 审中-公开
    用于显示核反应堆主电路的方法和装置

    公开(公告)号:WO2005040434A2

    公开(公告)日:2005-05-06

    申请号:PCT/FR2004002700

    申请日:2004-10-21

    Inventor: GILBERT RENE

    Abstract: The invention relates to a method which comprises filling the primary circuit (1) with water and setting the water pressure in said primary circuit (1) at a level allowing the operation of the primary pumps (15, 25, 35), operating the first primary pump (35) of a loop (33) which is not connected to the pressurizer (17) by a pressurization line (18), continuously exhausting the gas contained in the primary circuit (1) and carried by the water circulated by the pump (35) in the upper part of the vessel (12) at least during the primary pump operation, stopping the first primary pump (35) and successively operating the other primary pumps (25, 15) and, simultaneously, all the primary pumps (15, 25, 35) by simultaneously exhausting the gas in the upper part of said vessel (12) and carrying out the final venting of the primary circuit at the uppermost points of said primary circuit (1), by means of first and second exhaust lines (27, 22), respectively connected to the cover of the vessel (12) and to the pressurizer (17). Said invention also relates to a device comprising means for continuously exhausting gas reaching the upper part (12a) of the vessel (12) during the operation of the pumps.

    Abstract translation: 本发明涉及一种方法,其包括用初级回路(1)填充水并将所述主回路(1)中的水压设定在允许操作第一泵(15,25,35)的主泵 通过加压管线(18)未连接到加压器(17)的回路(33)的主泵(35)连续排出包含在主回路(1)中的气体并由泵循环的水 (35),并且连续地操作其它主泵(25,15),并且同时地将所有的主泵( 通过同时排出所述容器(12)的上部中的气体并且通过第一和第二排气在第一回路(1)的最上点处执行初级回路的最终排气, (27,22),分别连接到容器(12)的盖子上 )和加压器(17)。 所述发明还涉及一种装置,其包括用于在泵的操作期间连续排出到达容器(12)的上部(12a)的气体的装置。

    CONTAINMENT VESSEL DRAIN SYSTEM
    8.
    发明申请
    CONTAINMENT VESSEL DRAIN SYSTEM 审中-公开
    集装箱船排水系统

    公开(公告)号:WO2016122743A4

    公开(公告)日:2016-09-22

    申请号:PCT/US2015060144

    申请日:2015-11-11

    Inventor: HARRIS SCOTT G

    CPC classification number: G21C15/02 G21C13/022 Y02E30/40

    Abstract: A system for draining a containment vessel may include a drain inlet located in a lower portion of the containment vessel. The containment vessel may be at least partially filled with a liquid, and the drain inlet may be located below a surface of the liquid. The system may further comprise an inlet located in an upper portion of the containment vessel. The inlet may be configured to insert pressurized gas into the containment vessel to form a pressurized region above the surface of the liquid, and the pressurized region may operate to apply a surface pressure that forces the liquid into the drain inlet. Additionally, a fluid separation device may be operatively connected to the drain inlet. The fluid separation device may be configured to separate the liquid from the pressurized gas that enters the drain inlet after the surface of the liquid falls below the drain inlet.

    Abstract translation: 用于排放安全壳容器的系统可以包括位于安全壳容器下部的排放入口。 容纳容器可以至少部分地填充有液体,并且排水入口可以位于液体的表面下方。 该系统还可以包括位于安全壳上部的入口。 入口可以构造成将加压气体插入到安全壳中以在液体表面上方形成加压区域,并且加压区域可以操作以施加迫使液体进入排出口的表面压力。 另外,流体分离装置可以可操作地连接到排水入口。 流体分离装置可构造成在液体表面落入排水入口下方之后将液体与进入排水入口的加压气体分离。

    PASSIVE CONTAINMENT AIR COOLING FOR NUCLEAR POWER PLANTS
    9.
    发明申请
    PASSIVE CONTAINMENT AIR COOLING FOR NUCLEAR POWER PLANTS 审中-公开
    用于核电厂的被动容纳空气冷却

    公开(公告)号:WO2013158349A1

    公开(公告)日:2013-10-24

    申请号:PCT/US2013/034257

    申请日:2013-03-28

    Abstract: An enhanced passive containment air cooling system for a nuclear power plant that increases the heat transfer surface on the exterior of the nuclear plant's containment vessel. The increased surface area is created by forming a tortuous path in or on at least a substantial part of the exterior surface of the containment vessel over which a cooling fluid can flow and follow the tortuous path. The tortuous path is formed from a series of indentations and protrusions in or on the exterior surface that form a circuitous path for the cooling fluid.

    Abstract translation: 一个用于核电站的增强型无源遏制空气冷却系统,其增加了核电厂遏制容器外部的传热表面。 增加的表面积是通过在容纳容器的外表面的至少大部分内部或之上形成曲折路径而形成的,冷却流体可以在该容器的外表面上流动并跟随曲折路径。 曲折的路径由外表面上或外表面上的一系列凹陷和突起形成,形成用于冷却流体的迂回路径。

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